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Category:Regulatory Guide
MONTHYEARML23263A9972024-02-0202 February 2024
Watermarked - DG-5072 - Rev 0 of RG 5.90 - Guidance for Alternative Physical Security Requirements for Small Modular Reactors and Non-Light-Water Reactors
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Watermarked - DG-5074 - Access Authorization - Econcurrence Version Clean (02-03-23)
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Watermarked DG-5073 - Fitness for Duty Program for Part 53 - 10-13-23
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Draft Regulatory Guide DG-1404, Revision 1 (RG 1.253 Rev 0) Guidance on Ticap for Non-LWRs
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DG-1374 RG 1.152 Rev 4 Criteria for Programmable Digital Devices in Safety-Related Systems of Nuclear Power Plants
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DG-4027, Draft Regulatory Guide 4.2 Supplement 1, Preparation of Environmental Reports for Nuclear Power Plant License Renewal Applications, Revision 2
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Draft Regulatory Guide DG-1418 (RG 1.212 Rev 2), Sizing Large Lead-Acid Storage Batteries. (ACRS Copy)
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Rev.0, Fitness-for-Duty Programs for Commercial Power Reactor and Category I Special Nuclear Material Licensees
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Rev 3 ACRS Spent Fuel Heat Generation in an ISFSI
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DG-1389 (ACRS Version for 3-16-22 Meeting) - Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors
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Document to Support ACRS Subcommittee Meeting - Redline RG 1.57, Rev 3, Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components
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Watermark for ACRS Fc Meeting RG 1.9 Rev 5
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DG 1381 for Rev 0 of RG 1.244 - Control of Heavy Loads for Nuclear Facilities
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DG-1371, Proposed Rev 6 of RG 1.26, Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants
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Regulatory Analysis - DG 1381 - Control of Heavy Loads for Nuclear Facilities
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Draft for Acrs Review
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Rev. 2
ML20120A6292021-01-31031 January 2021
Operation and Maintenance Code Case Acceptability, ASME OM Code, Revision 4, (DG-1368)
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ASME Code Cases Not Approved for Use, Revision 7 (DG-1369)
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Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 20, (DG-1367)
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Rev 4 (Draft for ACRS Fc Review on 2-3-21)
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a Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion, RG 1.208, Revision 0
Regulatory Guide 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities2020-12-31031 December 2020
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Public Comment Resolutions on DG-1362 for RG 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities
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Results of Periodic Review of Regulatory Guide (RG) 1.78
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DG 1363 for Proposed Rev 4 to Regulatory Guide (RG) 1.105 - Setpoints for Safety-Related Instrumentation
Regulatory Guide 3.152020-07-31031 July 2020
Regulatory Guide 3.15. Rev 2, Standard Format and Content of License Applications for Receipt and Storage of Unirradiated Power Reactor Fuel and Associated Radioactive Material at a Nuclear Power Plant
Regulatory Guide 1.2362020-07-30030 July 2020
Draft for ACRS Review
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Response to Comments for RG 1.236 for ACRS
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Memo to OCA - for Revision 1 of Regulatory Guide 8.39, Release of Patients Administered Radioactive Material
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Draft Regulatory Guide DG-1287, an Approach for Plant-Specific, risk-Informed Decisionmaking: Technical Specifications
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Draft Regulatory Guide DG-5040, Urine Specimen Collection and Test Results Review Under 10 CFR Part 26, Fitness for Duty Programs.
ML19203A0892019-07-31031 July 2019
Assessment of the Continued Adequacy of Revision 2 of Regulatory Guide 1.99 - Technical Letter Report
2024-02-02
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U.S. NUCLEAR REGULATORY COMMISSION Revision 1 April 1989 REGULATORY GUIDE
OFFICE OF NUCLEAR REGULATORY RESEARCH
REGULATORY GUIDE 3.45 (Task CE 802-5)
NUCLEAR CRITICALITY SAFETY FOR STEEL-PIPE INTERSECTIONS CONTAINING
AQUEOUS SOLUTIONS OF FISSILE MATERIALS
A. INTRODUCTION
by the American National Standards Institute (ANSI)
Section 70.22, "Contents of Applications," of on April 3, 1987.
10 CFR Part 70, "Domestic Licensing of Special Nu- ANSI/ANS-8.9-1987 provides specifications for clear Material," requires that applications for a spe- pipe intersections containing homogeneous aqueous cific license to own, acquire, deliver, receive, possess, solutions of fissile materials. All dimensions are inter- use, or transfer special nuclear material contain pro- preted as nominal values of schedule 10 or heavier posed procedures to avoid accidental conditions of standard steel pipe. Only single columns with inter- criticality. This regulatory guide provides guidance for sections are considered in the standard. For multiple complying with this portion of the Commission's regu- columns or columns in the vicinity of other fissile ma- lations by describing procedures acceptable to the terials and the influence of environmental factors, the NRC staff for the prevention of criticality accidents in standard requires that experimental data or validated the storage and processing of aqueous solutions of fis- computational techniques be used to determine the sile materials in steel-pipe intersections.
safe configuration. Criteria and data provided are Any information collection activities mentioned based on criticality experiments and validated calcu- in this regulatory guide are contained as requirements lations that are generally applicable to homogeneous in 10 CFR Part 70, which provides the regulatory ba- aqueous solutions of fissile materials. Specific infor- sis for this guide. The information collection require- mation is included on fissile solutions containing ura- ments in 10 CFR Part 70 have been cleared under nium enriched in the 235U or 233 U isotope or pluto- OMB Clearance No. 3150-0009. nium and on uranium solutions having a 23U content not exceeding 5 weight-percent of the total uranium.
B. DISCUSSION
ANSI/ANS-8.9-1987, "Nuclear Criticality Safety
C. REGULATORY POSITION
Criteria for Steel-Pipe Intersections Containing Aque- ous Solutions of Fissile Material,"' was prepared by The nuclear criticality safety practices and guid- Subcommittee 8, Fissionable Materials Outside Reac- ance for calculating safe steel-pipe intersections for tors, of the Standards Committee of the American aqueous solutions of fissile materials contained in Nuclear Society. ANSI/ANS 8.9-1987 was approved ANSI/ANS-8.9-1987 provide procedures generally acceptable to the NRC staff for the prevention of
'Copies may be obtained from the American Nuclear Society, criticality accidents in the storage and processing of
555 N. Kensington Avenue, La Grange Park, IL 60525. aqueous solutions of fissile materials.
USNRC REGUIATORY GUIDES The guides are Issued in the following ten broad divisions:
Regulatory Guides are Issued to describe and make available to the pub- lic methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate techniques used by the 1. Power Reactors 6. Products staff in evaluating specific problems or postulated accidents, or to pro- 2. Research and Test Reactors 7. Transportation vide guidance to applicants. Regulatory Guides are not substitutes for 3. Fuels and Materials Facilities 8. Occupational Health regulations, and compliance with them is not required. Methods and 4. Environmental and Siting 9. Antitrust and Financial Review solutions different from those set out in the guides will be acceptable if 5. Materials and Plant Protection 10. General they provide a basis for the findings requisite to the Issuance or continu- ance of a permit or license by the Commission.
Copies of issued guides may be purchased from the Government Printing This guide was issued after consideration of comments received from Office at the current GPO price. Information on current GPO prices may the public. Comments and suggestions for improvements in these be obtained by contacting the Superintendent of Documents, U.S.
guides are encouraged at all times, and guides will be revised, as ap- Government Printing Office, Post Office Box 37082, Washington, DC
propriate, to accommodate comments and to reflect new information or 20013-70B2, telephone (202)275-2060 or (202)275-2171.
experience.
Written comments may be submitted to the Regulatory Publications Issued guides may also be purchased from the National Technical Infor- Branch, DFIPS, ARM, U.S. Nuclear Regulatory Commission, Washing- mation Service on a standing order basis. Details on this service may be ton, DC 20555. obtained by writing NTIS, 5285 Port Royal Road, Springfield, VA 22161.
D. IMPLEMENTATION
pipe intersections. Therefore, except in those cases in The purpose of this section is to provide informa- which the applicant proposes an acceptable alterna- tion to applicants regarding the NRC staff's plan for tive method for complying with the specified portions using this regulatory guide. of the Commission's regulations, the method de- These methods reflect the latest general NRC ap- scribed here will be used in the evaluation of submit- proach to criticality safety in the storage and process- tals for license applications submitted pursuant to ing of aqueous solutions of fissile materials in steel- 10 CFR Part 70.
3.45-2
VALUE/IMPACT STATEMENT
A draft value/impact statement was published for the final guide has not been prepared. A copy of with the proposed Revision 1 to Regulatory Guide the draft value/impact statement is available for in-
3.45 (Task CE 802-5) when the draft guide was pub- spection and copying for a fee at the Commission's lished for public comment in May 1988. No changes Public Document Room at 2120 L Street NW., Wash- were necessary, so a separate value/impact statement ington, DC, under Task CE 802-5.
3.45-3
UNITED STATES FIRST CLASS MAIL
NUCLEAR REGULATORY COMMISSION POSTAGE b FEES PAID
USNRC
WASHINGTON, D.C. 20555 PERMIT No. G,67 OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE, $300